ML20210A860
| ML20210A860 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 01/30/1987 |
| From: | Conte R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Blough A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| NUDOCS 8702090030 | |
| Download: ML20210A860 (4) | |
Text
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s JAN 3 01987 Docket No. 50-289 MEMORANDUM FOR: Allen R. Blough, Chief Projects Branch No. 1, DRP FROM:
Richard J. Conte, Chief Reactor Projects Section IA, DRP
SUBJECT:
TMI-1 STATUS REPORT FOR THE PERIOD JANUARY 9 - 23, 1987 Enclosed is the biweekly status report from the NRC Resident Office at TMI-1 for the subject period. During this two week period, the NRC staff continued to monitor routine plant operatfor.s during cold shutdown and associated outage activities.
TMI-1 status reports are intended to provide NRC management and the public with highlights from an NRC regulatory perspective of TMI-1 activities for the pre-vious two weeks.
Original SLSned Eys Richard J. Conte, Chief t
Reactor Projects Section 1A Branch 1, DRP i
Enclosure:
As stated l
i 1
0FFICIAL RECORD COPY TMIl WEEKLY STATUS REPORT -
Ohh0h289 11/29/80 R 3 (
DR DO PDR I{
i A. Blough 2
cc w/ enclosure:
F. Miraglia, NRR W. Travers, NRR J. Thoma, NRR J. Partlow, IE T. Gerusky, BRP/ DER, Commonwealth of Pennsylvania R. Benko, Governor's' Office of Policy, Commonwealth of Pennsylvania TMI Alert Susquehanna Valley Alliance Friends & Family of TMI H. Hucker A. Herman C. Wolfe J. Johnsrud P. Smith E. Harzler D. Davenport H. Spinelli Concerned Mothers and Women Public Document Room Local Public Document Room bec w/ enclosure:
K. Abraham, RI P. Lohaus, RI W. Kane, RI F. Young, RI (20 cys)
W. Baunack, RI Region I Docket Room (w/ concurrences)
Rd RI:DRP 1
fp Yo g Conte Blough 1
/87 1/gM/87 1/3/87 OFFICIAL RECORD COPY TMIl WEEKLY STATUS REPORT -
11/29/80
[
3 ENCLOSURE TMI-1 STATUS REPORT FOR THE PERIOD JANUARY 9 - 2.$, 1987 1.
Plant Status As of 8:00 a.m. on January 23, 1987, TMI-1 was in cold shutdown on the 1B-Train of Decay Heat Removal with reactor coolant temperature at 105* F and 0 psig RCS pressure. Water level in the refueling transfer canal is being maintained approximately 23 feet above the reactor vessel (RV) flange.
2.
Facility Work Summary The plant was maintained in cold shutdown throughout the period. The li-censee completed the fuel shuffle portion of the refueling process. The refueling cavity remains full to provide for backup decay heat removal as maintenance is being accomplished on the non-operating "B" decay heat cool-ing loop. The "A" emergency diesel generator is being reassembled following repairs resulting from the engine damage that occurred during testing after the initial overhaul (see paragraph 3 below for additional details). Work continues on modifications with respect to upgrading the fire protection and the emergency feedwater (EFW) systems.
The licensee continued work on major secondary components; i.e., the main turbine and main feedwater pumps. At present, planned outage work is on schedule in anticipation of a late March 1987 startup.
3.
Items of Special Interest Emergency Diesel Generator Damage The licensee experienced damage to the "1A" emergency diesel generator during post-maintenance testing during the January 10-11, 1987, weekend.
The root cause has not yet been determined.
Prior to this time the diesel engine had been extensively overhauled during the annual inspection. The twelve engine cylinder liners had been replaced.
This was accomplished because a small jacket coolant leak into the cylinder was observed on one cylinder during the previous annual inspection in November 1985.
j During an 8-hour full load test at 3,000 kw, a small leak on one fuel in-jector occurred. This required a shutdown of the engine. Subsequent in-spection of one cylinder liner through an inspection port revealed severe cylinder wall damage.
The engine was disassembled and a more detailed evaluation was performed.
Several lower pistons and the associated liners were excessively scored or showed burn marks. The piston rings showed excessive wear.
Several connecting rod wrist pins and associated bushings were worn or damaged.
The licensee is presently reassembling the engine and testing will follow. An evaluation of the cause of this problem is being pursued by the licensee and vendor.
OFFICIAL RECORD COPY TMIl WEEKLY STATUS REPORT -
11/29/80
O g
2 Enclosure 4.
Systematic Assessment of Licensee Performance (SALP)
The NRC Region I SALP board met on December 3, 1986, to discuss licensee performance between May 1, 1986, and October 31, 1986. This report was issued on January 5, 1987, and copies of this document are available from the TMI-1 NRC Resident Office.
To obtain a copy of the SALP report, members of the general public may contact Ms. C. Hix at 948-1160 during the hours of 7:00 a.m. to 3:30 p.m.
This SALP is the third of three SALP reports conducted by Region I in 1986 and the final report for the two Commission directed SALP's in their restart order.
A management meeting between NRC and GPUN to discuss the SALP is scheduled for February 24, 1987 at 1:00 p.m. in the GPU Nuclear Media Center, 99 South Cameron Street, Harrisburg, PA. The meeting is open to the public but the public may not participate.
Further a meeting between NRC staff and members of the public is scheduled for 7:00 p.m., February 24, 1987, to discuss comments and questions on the SALP Report and the management meeting held earlier in the day. The meeting is to be held at the NRC's Middletown Office,100 Brown Street (at the Downtown Mall) in Middletown, PA.
Because of space limitations, anyone interested in attending either meeting on February 24, 1987 should contact R. Conte at (717) 948-1167 or at
~
(215) 337-5146.
5.
NRC Staff Activities During the Period During this report period, the NRC staff consisted of two resident inspec-tors. One region-based inspector was on site to conduct a review of control rcom habitability and EFW modifications.
A Region I team inspection was conducted at the licensee's corporate office in Parsippany, New Jersey during the week of January 12, 1987 and on site on January 20-21, 1987. The inspection reviewed the licensee's Environmental Qualification (EQ) program. This inspection will be documented at a later date in Inspection Report No. 50-289/87-01.
The NRC staff at TMI-1 was comprised of the following personnel during the j
period.
L. Chung, Reactor Engineer, Region I (RI) (part time)
O. Gormely, Inspection Specialist, NRC Headquarters (part time)
C. Hix, Secretary l
D. Johnson, Resident Inspector l
F. Paulitz, Reactor Engineer, RI (part time)
R. Paolino, Reactor Engineer, RI (part time) l J. Rogers, Resident Inspector l
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